JP2015004595A - Radioactive substance adsorbent disposal system and disposal method of radioactive substance adsorbent - Google Patents

Abstract

PROBLEM TO BE SOLVED: To efficiently dispose of radioactive substance adsorbent which contains ferrocyanide with adsorbed radioactive matter while efficiently preventing elution of free cyanide from the disposed radioactive substance adsorbent.SOLUTION: The radioactive substance adsorbent disposal system disposes radioactive substance adsorbent containing ferrocyanide with adsorbed radioactive matter. The radioactive substance adsorbent disposal system has an addition section. The addition section adds hydrotalcite-like material of a crystal element to the radioactive substance adsorbent with radioactive matter.

Description

  Embodiments described herein relate generally to a radioactive material adsorbent disposal apparatus and a radioactive material adsorbent disposal method.

  Various methods have been proposed for recovering and immobilizing radioactive materials from incinerated ash containing radioactive materials such as radioactive cesium.

  For example, radioactive cesium is recovered by using a zeolitic mineral such as mordenite as a radioactive substance adsorbent. In this case, a large amount of zeolitic mineral is used, which increases the cost and the amount of waste. For this reason, it has been attempted to use ferrocyanide such as Prussian blue (bitumen (ferric ferrocyanide)) as an adsorbent for radioactive substances instead of zeolitic minerals.

Ferrocyanide can be mass-produced economically and has a small dissociation constant ( ^{K≈10 −36} ) of CN ⁻ . In addition, ferrocyanide has a high adsorbability for adsorbing radioactive substances such as radioactive cesium. For this reason, ferrocyanides are frequently used.

Japanese Patent No. 4588798 Japanese Patent No. 3867306 Japanese Patent No. 4374602 Japanese Patent No. 5024876 Japanese Patent No. 2961358 Japanese Patent No. 311574 Japanese Patent No. 3929293

  However, ferrocyanides may release free cyanides at high concentrations in environments with high pH, exposure to ultraviolet light, and reducing atmospheres.

  As measures against free cyanide, it is known to decompose cyanide by oxidative decomposition, biodegradation, and photolysis. In addition, it is known to separate free cyanide by precipitation separation, gas layer separation, and two-layer separation using a reverse osmosis membrane. In addition to this, as in the case of storing radioactive waste, it can be confined in a metal structure or a concrete structure, or buried and disposed of in the ground.

  However, in the above method, it may be difficult to efficiently dispose of the radioactive material adsorbent on which the radioactive material is adsorbed.

  Therefore, the problem to be solved by the present invention is that when a radioactive material adsorbent containing a ferrocyanide adsorbed with a radioactive substance is disposed of, the elution of free cyanide is effectively suppressed, and the radioactive substance adsorbent is efficiently The present invention provides a radioactive material adsorbent disposal apparatus and a radioactive material adsorbent disposal method that can be disposed of.

  The radioactive substance adsorbent disposal apparatus of the embodiment disposes of a radioactive substance adsorbent containing a ferrocyanide adsorbed with a radioactive substance. Here, the radioactive substance adsorbent disposal apparatus has an addition part, and the addition part adds the hydrotalcite-like substance to the radioactive substance adsorbent to which the radioactive substance is adsorbed.

  According to the present invention, when disposing of a radioactive material adsorbent containing ferrocyanide adsorbed with a radioactive substance, it is possible to efficiently suppress elution of free cyanide and to dispose of the radioactive substance adsorbent efficiently. In addition, a radioactive substance adsorbent disposal apparatus and a radioactive substance adsorbent disposal method can be provided.

FIG. 1 is a diagram schematically illustrating a radioactive waste processing apparatus according to an embodiment. FIG. 2 is a flowchart illustrating the adsorbent disposal method according to the embodiment.

  Embodiments will be described with reference to the drawings.

[A] Configuration FIG. 1 is a diagram schematically illustrating a radioactive waste processing apparatus according to an embodiment.

  As shown in FIG. 1, the radioactive waste treatment apparatus 1 includes a radioactive substance elution part 10, a radioactive substance adsorption part 20, and an adsorbent disposal part 30 (radioactive substance adsorbent disposal apparatus).

  Hereinafter, details of each unit constituting the radioactive waste treatment apparatus 1 will be sequentially described.

[A-1] Radioactive substance elution part 10
As shown in FIG. 1, the radioactive substance elution part 10 has a dissolution tank 11 and a filter 12, and elutes the radioactive substance from the incineration ash F14 such as fly ash containing the radioactive substance.

  Specifically, in the radioactive substance elution unit 10, the dissolution tank 11 is supplied with the solvent F13 from the solvent supply unit 13. At the same time, the incineration ash F14 containing a radioactive substance is supplied to the dissolution tank 11 from the incineration ash supply unit 14.

  The solvent F13 is preferably one in which the radioactive substance is sufficiently dissolved and the dissolution of other ions is suppressed according to the composition of the incineration ash F14. For example, water is supplied from the solvent supply unit 13 as the solvent F13. . Further, as the incineration ash F14, for example, one containing radioactive cesium exceeding 8000 Bq / kg is supplied.

  Moreover, the agitator 15 is installed in the dissolution tank 11, and the solvent F <b> 13 into which the incineration ash F <b> 14 is charged is agitated above the filter 12 by the agitator 15. Thereby, the incineration ash F14 is mixed in the solvent F13, and a radioactive substance such as radioactive cesium contained in the incineration ash F14 is separated from the incineration ash F14 and dissolved in the solvent F13.

  In the radioactive substance elution unit 10, the filter 12 is installed inside the dissolution tank 11. Here, the filter 12 is supported inside the dissolution tank 11 such that the lower surface of the filter 12 faces with a gap from the bottom plate of the dissolution tank 11. The filter 12 is configured not to pass the incinerated ash F14 downward but to pass downward the solvent F13 in which the radioactive substance is dissolved.

[A-2] Radioactive material adsorption part 20
As shown in FIG. 1, the radioactive substance adsorption unit 20 includes an adsorption tank 21, a filter 22, and an adsorbent 23, and adsorbs the radioactive substance eluted by the radioactive substance elution part 10.

  Specifically, in the radioactive substance adsorbing unit 20, the adsorption tank 21 has a supply port 211, a first discharge port 212A, and a second discharge port 212B. In the adsorption tank 21, the supply port 211 and the first discharge port 212A face each other in the horizontal direction. In the adsorption tank 21, the second discharge port 212 </ b> B is located between the supply port 211 and the first discharge port 212 </ b> A, and is provided in the lower portion of the adsorption tank 21.

  In the radioactive substance adsorption unit 20, the filter 22 is installed inside the adsorption tank 21. Here, the filter 22 is fixed between the first outlet 212A and the second outlet 212B. The filter 22 is configured so that the solvent F13 supplied to the inside of the adsorption tank 21 passes without passing the adsorbent 23.

  In the radioactive substance adsorbing unit 20, the adsorbent 23 is filled in the adsorption tank 21. Here, the adsorbent 23 is filled in a space located on the supply port 211 side from the filter 22.

In this embodiment, a ferrocyanide such as Prussian blue (bitumen (ferric ferrocyanide)) represented by the chemical formula MFe [Fe (CN) ₆ ] (M = K, Na, NH ₄ ^+, etc.) is supported. The particles are filled into the adsorption tank 21 as the adsorbent 23.

Further, as the particles carrying the ferrocyanide, those formed below are preferable.
・ Polyacrylonitrile ・ Activated carbon ・ Titanium oxide

  In the radioactive substance adsorbing unit 20, first, the solution F <b> 10 in which the radioactive substance is dissolved in the adsorption tank 21 of the radioactive substance eluting unit 10 flows from below the filter 12 into the supply port 211 of the adsorption tank 21 through the pump P <b> 10. . Then, in the adsorption tank 21, the radioactive substance dissolved in the solution F10 is adsorbed and removed by the adsorbent 23. Then, the solution F10 that sequentially passes through the adsorbent 23 and the filter 22 inside the adsorption tank 21 flows out from the first discharge port 212A to the outside as the radioactive component removal liquid F20A. In addition, the adsorbent paste F20B in which the solution F10 and the adsorbent 23 are mixed flows out from the second outlet 212B.

  The radioactive substance adsorbing unit 20 adsorbs the solution F10 that sequentially passes through the adsorbent 23 and the filter 22 so that the adsorbent 23 can be replaced before the concentration of the radioactive substance exceeds a predetermined value. A tank 21 is configured.

[A-3] Adsorbent disposal unit 30 (radioactive material adsorbent disposal device)
As shown in FIG. 1, the adsorbent disposal unit 30 includes a drying unit 31, an addition unit 32, and a molding unit 33. The adsorbent disposal unit 30 disposes the adsorbent 23 on which the radioactive substance is adsorbed by the radioactive substance adsorption unit 20. .

[A-3-1] Drying unit 31
In the adsorbent disposal unit 30, the drying unit 31 dries the adsorbent paste F20B supplied from the radioactive substance adsorbing unit 20.

  Specifically, the drying unit 31 includes a dryer 311, and the adsorbent paste F <b> 20 </ b> B flowing out from the second discharge port 212 </ b> B in the adsorption tank 21 of the radioactive material adsorption unit 20 is supplied to the inside from the inlet 312 of the dryer 311. Is done. Then, the adsorbent paste F20B is dried by applying heat to the adsorbent paste F20B inside the dryer 311. By this drying, chlorine is removed together with dehydration. In the drying unit 31, the adsorbent F31 obtained by the drying is discharged from the outlet 313 to the outside.

[A-3-2] Addition unit 32
In the adsorbent disposal unit 30, the addition unit 32 adds the additive to the adsorbent F31 obtained by drying in the drying unit 31. Here, the addition unit 32 adds, as an additive, a material that adsorbs free cyanide liberated from the ferrocyanide contained in the adsorbent F31.

  In this embodiment, the addition part 32 adds each of hydrotalcite-like substance F32A and normal Portland cement F32B as an additive which adsorb | sucks free cyan | cyanogen.

  Specifically, the addition unit 32 includes a mixer 321, and the powdery adsorbent F 31 is supplied from the drying unit 31 to the tank of the mixer 321. Then, the hydrotalcite-like substance F32A is supplied to the tank of the mixer 321 from the first additive supply unit 32A. Furthermore, normal Portland cement F32B is supplied to the tank of the mixer 321 from the second additive supply unit 32B. Then, the adsorbent F31 supplied with the hydrotalcite-like substance F32A and the ordinary Portland cement F32B is stirred and mixed by the mixer 321.

  The hydrotalcite-like substance F32A added in the addition part 32 is a substance containing a “hydrotalcite structure” and is a clay mineral.

  Specifically, the hydrotalcite-like substance F32A is represented by the following general formula (A).

[M _1-x ²⁺ M _x ³⁺ (OH) ₂ ] ^{x +} [A ⁿ⁻ _{x / n} · mH ₂ O] ^x− (A)
^{M 2+: Mg 2+, Ni 2+} , Zn 2+, Fe 2+, Ca 2+, 2 -valent metal ions M ³⁺ of ^{Cu 2+} or the like: ^Al 3+, 3-valent metal ion A of ^{Fe 3+,} etc. ^n-: _CO ³ 2-, Cl ⁻ , NO ₃ ^{— and the} like n-valent anions x: 0 <x ≦ 0.33

Hydrotalcite-like material F32A is a divalent metal ^{M 2+} (in particular, Mg ion ^{(Mg 2+))} octahedral (brucite layers) centered on is continuous to two-dimensionally, divalent part of the metal ^{M 2+ Are} replaced by a trivalent metal M ³⁺ (particularly, Al ions (Al ³⁺ )) to form a layered structure.

Since the hydrotalcite-like substance F32A is an inorganic compound, it has excellent long-term stability. In particular, when M ²⁺ is Mg ²⁺ in the general formula (A), the rate of migration to the liquid layer (migration rate) is low, so that the structural stability when in contact with the aqueous phase is excellent.

Further, the hydrotalcite-like substance F32A holds an anion (particularly, carbonate ion (CO ₃ ²⁻ )) between layers, and adsorbs CN ⁻ by substitution of the anion. In particular, the anion adsorption performance can be improved by performing a decarboxylation treatment by heating.

On the other hand, normal Portland cement F32B added in the addition part 32 is prescribed | regulated in JISR5210. Ordinary Portland cement F32B contains oxides of Ca, Si, Fe, and Al as main components, and the concentration of MgO and Al ₂ O ₃ that affect pre-hardening are different. Lower than that of the kind. For this reason, it is formed with a dense composition.

Ordinary portland cement F32B is a major component Ca, the positive charge due to Si is appearing on the particle surface, CN its positive charge ^- anions like are electrically adsorbed.

[A-3-3] Molding part 33
In the adsorbent disposal unit 30, the molding unit 33 performs molding on the mixture F32 in which the adsorbent F31, the hydrotalcite-like substance F32A, and the ordinary Portland cement F32B are mixed in the addition unit 32.

  Specifically, the molding unit 33 includes a compression molding machine 331, and the mixture F32 is supplied from the addition unit 32 to the inlet 332 of the compression molding machine 331. In the compression molding machine 331, the supplied mixture F32 is compressed and molded. Then, the molded body F33 thus molded is discharged from the outlet 333 of the compression molding machine 331 and accommodated in a container 34 such as a drum can.

[B] Adsorbent Disposal Method FIG. 2 is a flowchart showing the adsorbent disposal method according to the embodiment.

  A method for disposing of an adsorbent containing ferrocyanide adsorbed with a radioactive substance will be described in detail with reference to FIG.

[B-1] Drying of Adsorbent As shown in FIG. 2, the adsorbent is first dried (ST1).

  Here, as shown in FIG. 1, the adsorbent paste F <b> 20 </ b> B flows from the adsorption tank 21 of the radioactive substance adsorbing unit 20 into the drying unit 31 of the adsorbent disposal unit 30. Specifically, the adsorbent paste F20B flows into the drying unit 31 together with the particles carrying the ferrocyanide. Then, the adsorbent paste F20B is dried by the drying unit 31 (see FIG. 1).

For example, drying is performed under the following drying conditions using a centrifugal thin film dryer.
(Drying conditions)
-Drying temperature: 150 ° C or higher and 220 ° C or lower-Drying time: Several seconds or longer, 10 seconds or shorter

[B-2] Addition of additive Next, as shown in FIG. 2, an additive is added (ST2).

  Here, as shown in FIG. 1, each of the powder of hydrotalcite-like substance F32A and the powder of normal Portland cement F32B is added to the powder of adsorbent F31 obtained by drying. Add in part 32. That is, an additive that adsorbs free cyanide liberated from the ferrocyanide contained in the adsorbent F31 is added.

The addition ratio of the hydrotalcite-like substance F32A is preferably in the following range.
(Addition ratio of hydrotalcite-like substance F32A)
-10 wt% or more and 20 wt% or less When it is smaller than this range, there is a case where adsorption of free cyanide cannot be performed sufficiently. On the other hand, if it is less than this range, there may be a problem of increased waste.

The following range is preferable for the proportion of ordinary Portland cement F32B added.
(Addition ratio of normal Portland cement F32B)
-10 wt% or more and 20 wt% or less If it is smaller than this range, solidification may not be performed sufficiently. On the other hand, if it is larger than this range, there may be a problem of increased waste.

[B-3] Molding Next, molding is performed as shown in FIG. 2 (ST3).

  Here, as shown in FIG. 1, a mixture F <b> 32 in which the adsorbent F <b> 31, the hydrotalcite-like substance F <b> 32 </ b> A, and ordinary Portland cement F <b> 32 </ b> B is mixed in the addition unit 32 is molded in the molding unit 33. For example, the molding is performed under the condition that the pressure is 10 MPa and the compression time is 1 minute. And the molded object F33 shape | molded in the shaping | molding part 33 is accommodated in containers 34, such as a drum can. The container 34 is transported to a disposal site.

[C] Example [C-1] Measurement Result of Sorption Distribution Coefficient From the following, the results of measuring the sorption distribution coefficient of free cyanide for the hydrotalcite-like substance and the additive for ordinary Portland cement are shown.

  Here, the sorption distribution coefficient was measured according to “Method of measuring sorption distribution coefficient” defined in AESJ-SC-F003: 2002.

(1) First, an aqueous KCN solution was prepared ([KCN] = 2 × 10 ⁻⁴ mol / L).

(2) Next, an additive (hydrotalcite-like substance, ordinary Portland cement) was added to the KCN aqueous solution (liquid-solid ratio 100).

(3) Next, the pH of the KCN aqueous solution was adjusted. Here, adjustment was performed using a NaOH aqueous solution so that the KCN aqueous solution had a pH of 9 or more.

(4) Next, the KCN aqueous solution was shaken (at room temperature (28 to 33 ° C.) for 1 week or longer (168 hours)).

(5) Next, after allowing the KCN aqueous solution to stand (15 minutes or more), the KCN aqueous solution was filtered. Here, 0.45 μm mesh filter paper was used.

(6) Next, the concentration of free cyanide contained in the filtered KCN aqueous solution was measured. Here, this measurement was performed by “4-pyridinecarboxylic acid-pyrazolone absorptiometry (JIS K 0102 38.3)”.

  Table 1 shows the results of measuring the sorption distribution coefficient Kd of free cyanide for hydrotalcite-like materials and ordinary Portland cement.

  As shown in Table 1, it can be seen that hydrotalcite-like substances and ordinary Portland cement have a high sorption distribution coefficient Kd of free cyanide. In particular, the hydrotalcite-like substance has a sorption distribution coefficient Kd of free cyan of 1200 mL / g and is a four-digit value, so that it can be effectively used as an adsorbent of free cyanide. Moreover, since ordinary Portland cement has lower pre-hardness than other cements, the composition of the cured product can be made dense.

[C-2] Results of Cyan Dissolution Test From the following, results of conducting a cyan dissolution test on a sample obtained by adding each of hydrotalcite-like substance and ordinary Portland cement as additives to an adsorbent containing ferrocyanide. Indicates.

Here, as the adsorbent containing ferrocyanide, the following particles having the following ferrocyanide supported thereon were prepared. Then, pure water was added to the adsorbent so as to obtain the following liquid-solid ratio.
-Ferrocyanide-Prussian blue-Particles-Polyacrylonitrile (average particle size 0.6-0.8 mm)
・ Liquid-solid ratio: 10mL / g

  And a hydrotalcite-like substance and normal Portland cement were added to said adsorbent. Here, the hydrotalcite-like substance was added to 3.0 wt%, and ordinary Portland cement was added to 4.6 wt%. Then, the density | concentration of free cyan | cyanogen was calculated | required by performing the procedure similar to the procedure (4)-(6) shown in the above-mentioned "measurement method of a sorption distribution coefficient." However, in order to remove Prussian blue, 0.03 mesh filter paper was used.

In addition, as a comparative example, the concentration of free cyanide was determined for the case where a hydrotalcite-like substance and ordinary Portland cement were not added. In this case, Ca (OH) ₂ was added separately (pH = 12.5) in order to adjust to the pH when ordinary Portland cement was added.

  Table 2 shows the results of a cyan elution test performed on samples obtained by adding a hydrotalcite-like substance and ordinary Portland cement to an adsorbent containing ferrocyanide.

  As shown in Table 2, free cyanide can be effectively adsorbed by adding a hydrotalcite-like substance and ordinary Portland cement to an adsorbent containing ferrocyanide.

  The hydrotalcite-like substance is buffered near pH. For this reason, since the pH of the mixture of the hydrotalcite-like substance and the ferrocyanide is not extremely high, decomposition of the ferrocyanide can be suppressed and elution of cyanide can be suppressed.

[C-3] Test Results of Molded Body Hereinafter, test results of the molded body F33 (see FIG. 1) will be described.

  Here, the hydrotalcite-like substance was added to the adsorbent prepared in the “cyan elution test” so as to be 5 wt%, and ordinary Portland cement was added so as to be 3 wt% and mixed. And after compressing and molding the mixture based on the rule of JIS A1107, the molded body was tested for “apparent density” and “uniaxial compressive strength”.

  In addition, as a comparative example, a test was similarly conducted for the case where a hydrotalcite-like substance and ordinary Portland cement were not added.

  Table 3 shows the test results of “apparent density” and “uniaxial compressive strength”.

  When the true specific gravity of the adsorbent containing the ferrocyanide is 1.0 to 1.2, as shown in Table 3, when a hydrotalcite-like substance and ordinary Portland cement are added, The apparent density is 90% or more. For this reason, there is almost no increase in volume.

  At the same time, when hydrotalcite-like substances and ordinary Portland cement are added, the uniaxial compressive strength is “A policy on the disposal method of incineration ash etc. exceeding 8000 Bq / kg and less than 100,000 Bq / kg”. Satisfies the reference value (0.98 MPa or more) defined in Japanese Patent No. 110831001).

[D] Summary As described above, in the present embodiment, the adsorbent disposal unit 30 (radioactive material adsorbent disposal apparatus) processes the adsorbent containing the ferrocyanide adsorbed with a radioactive material such as radioactive cesium.

  In this embodiment, the hydrotalcite-like substance F32A is added to the adsorbent F31 on which the radioactive substance is adsorbed (see FIG. 1). For this reason, in this embodiment, as described above, the hydrotalcite-like substance F32A adsorbs free cyanide liberated from the ferrocyanide. As a result, in this embodiment, since the structure of the ferrocyanide is maintained and elution of free cyanide is efficiently suppressed, the radioactive material adsorbent can be disposed of efficiently.

  In the present embodiment, ordinary Portland cement F32B is added to the adsorbent F31 adsorbed with the radioactive substance in addition to the hydrotalcite-like substance F32A (see FIG. 1). For this reason, in this embodiment, as above-mentioned, normal Portland cement F32B adsorb | sucks the free cyan | cyanogen released from a ferrocyanide. As a result, in this embodiment, since the structure of the ferrocyanide is maintained and elution of free cyanide is efficiently suppressed, the radioactive material adsorbent can be disposed of efficiently. Furthermore, when normal Portland cement F32B is added, the increase in volume can be suppressed and solidified by the solidification action by the polazone reaction and the hydration reaction of the calcium compound.

  In this embodiment, a mixture in which an adsorbent, a hydrotalcite-like substance, and ordinary Portland cement are mixed is molded (see FIG. 1). For this reason, in this embodiment, since a surface area and a volume can be reduced, the burden of disposal can be reduced.

[E] Modification In the above embodiment, the adsorbent paste F20B is continuously supplied from the radioactive substance adsorbing unit 20 to the adsorbent disposal unit 30, and the adsorbent paste F20B is continuously supplied to the adsorbent disposal unit 30. Shown for processing. However, it is not limited to this. The adsorbent contained in the radioactive substance adsorbing unit 20 may be configured to be processed in a “batch type” instead of being processed in the “continuous type” in the adsorbent disposal unit 30. Specifically, in the radioactive substance adsorbing unit 20, before the concentration of the radioactive substance exceeds a predetermined value for the solution F <b> 10 that sequentially passes through the adsorbent 23 and the filter 22, the adsorbent 23 is adsorbed from the radioactive substance adsorbing unit 20. Take out. Then, the extracted adsorbent 23 is subjected to the same processing as described above and disposed of.

  In the above embodiment, the case where both the hydrotalcite-like substance and ordinary Portland cement are added to the adsorbent containing ferrocyanide has been described, but the present invention is not limited thereto. For example, a hydrotalcite-like substance is added, and normal portland cement may not be added.

<Others>
Although several embodiments of the present invention have been described, these embodiments are presented by way of example and are not intended to limit the scope of the invention. These novel embodiments can be implemented in various other forms, and various omissions, replacements, and changes can be made without departing from the scope of the invention. These embodiments and modifications thereof are included in the scope and gist of the invention, and are included in the invention described in the claims and the equivalents thereof.

DESCRIPTION OF SYMBOLS 1 ... Radioactive waste processing apparatus, 10 ... Radioactive substance elution part, 11 ... Dissolution tank, 12 ... Filter, 13 ... Solvent supply part, 14 ... Incineration ash supply part, 15 ... Stirrer, 20 ... Radioactive substance adsorption part (radioactive substance) (Material adsorbent disposal apparatus), 21 ... adsorption tank, 22 ... filter, 23 ... adsorbent, 30 ... adsorbent disposal section, 31 ... drying section, 32 ... addition section, 32A ... first additive supply section, 32B ... first 2 additive supply part, 33 ... molding part, 34 ... container, 211 ... supply port, 212A ... first discharge port, 212B ... second discharge port, 311 ... dryer, 312 ... inlet, 313 ... outlet, 321 ... mixer 331 ... compression molding machine, 332 ... inlet, 333 ... outlet, F10 ... solution, F13 ... solvent, F14 ... incinerated ash, F20A ... radioactive component removing liquid, F20B ... adsorbent paste, F31 ... adsorbent, F32 ... mixture, F32A Hydrotalcite-like substance, F32B ... ordinary portland cement, F33 ... the molded body, P10 ... pump

Claims (6)

A radioactive material adsorbent disposal device for disposing of a radioactive material adsorbent containing ferrocyanide adsorbed with a radioactive material,
It has an addition part for adding a hydrotalcite-like substance to the radioactive substance adsorbent adsorbed by the radioactive substance,
Radioactive material adsorbent disposal equipment. In addition to the hydrotalcite-like substance, the addition part is characterized by adding ordinary Portland cement to the radioactive substance adsorbent adsorbed by the radioactive substance.
The radioactive substance adsorbent disposal apparatus according to claim 1. The addition part has a molding part for molding a mixture in which the radioactive substance adsorbent and at least the hydrotalcite-like substance are mixed,
The radioactive substance adsorbent disposal apparatus according to claim 1 or 2. A radioactive material adsorbent disposal method for disposing of a radioactive material adsorbent containing ferrocyanide adsorbed with a radioactive material,
An addition step of adding a hydrotalcite-like substance to the radioactive substance adsorbent adsorbed by the radioactive substance,
Disposal method of radioactive material adsorbent. In the addition step, in addition to the hydrotalcite-like substance, ordinary Portland cement is added to the radioactive substance adsorbent adsorbed by the radioactive substance.
The disposal method of the radioactive substance adsorbent of Claim 4. In the addition step, the method includes a molding step of molding a mixture in which the radioactive substance adsorbent and at least the hydrotalcite-like substance are mixed.
The disposal method of the radioactive substance adsorbent of Claim 4 or 5.

Images